ML20003A188
| ML20003A188 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 01/11/1977 |
| From: | Sewell R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8101300830 | |
| Download: ML20003A188 (9) | |
Text
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f P0Yl8r C0mpBDy c.n r.i ome..; 952 w..e unemo.n Avenue.saca.on. M8CNGen 49201 e Area Cod. S17 788 OSSO January 11, 1977
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DCCCT 50-155, LICE;SI DPR di] hy BIG ROCK POINT PL/JIT On August 31,1976 (with corrections dated September 15, 1976), consumers Power Co=pany tranc=itted radioactive effluent su== aries for the Big Rock Point Plant in accordance with the requirements of 10 CFR 50 36.s(2). Due to an cversight, we did not include infor=ation regarding radioactive vecte shipments and rsdio-logical environmental monitoring, as required by Technical Specification Section 6.9 3 This information is transmitted attached and should be added to the effluent su== aries submitted August 31, 1976.
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Radioactive Waste Shipments During the period of January thru June 1976, seven shipments of radioactive material left the site. Two shipments involved exempt quantities and two others were irradiated cobalt totaling approximately 575,000 Curies. Of the remaining three shipments (epproximately 0.lf+ Curie) only one involved solid waste for burial. The following table lists all shipments for the period.
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m OFF-SITE SHIPMErrI'S OF RADI0 ACTIVE MATERIAL SHIIMFNT NUMBER DATE TRt.NSFERRED FROM TRANSFERRED 'IO RADIOACTIVE MATERIAL VOLUME DISIOSITION 393 2/20/76 DPR-6 Ginna Station Fuel Insp Tools 2 ft3 Reuse (Exempt Quantity)
(0.16pCi) 394 3/11/76 DPR-6 Exxon, Richland, WA Fuel Insp Tools 6 ft3 Reuse WN-I-062-1 (4.98 mci) 395 3/17/76 DPR-6 Battelle, Columbus, OH 16 Co-60 Rods
<1 ft3 Processing i
34-06854-05 (287,000 C1) 3%
3/22/76 DPR-6 NES, Bockville, MD Carbon filter crud 1 ft3 Analyses (Exempt Quantity)-
samples (4100pCi) 397 4/21/76 DPR-6 Battelle, Columbus, OH Steam drum relief 5 ft3 Examination 34-06854-05 Valve nozzles (300 mC1) 398 4/29/76 DPR-6 Battelle, Columbus, Oh 19 Co-60 aods
< 1 ft3 Processing 34-06854-05 (287,565C1) 3
~/20/76 DPR-6 NECO, Morehead, KY 123 DDT 17H Barrels 918 ft Burial 5
399 16-NSF-1 (0.13C1)
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Radiological Environmental Monitoring Program Tables 1 and 2 summarize the results of the radiological environmental monitor-ing program for the first six months of 1976. The only two locations at which levels were found to be significantly above local background were the plant in-take and discharge. Table 3 compares the measured intake and discharge gross beta activity to that calculated fmm effluent data. The calculated average monthly discharge concentrations do not congare well with the measured concen-tration. This is due in part to 'a fixed sampling rate while the discharge flow varies significantly during each sampling period (see Table 3). The aver-age for the first six months, however, is within a factor of two of calculated concentration for the period. This is considered reasonable for this type of data. The high intake concentrations are believed due to the use of a warning line from the discharge to the intake for prevention of ice buildup. Table 4 contains the results of isotopic analysis of the intake and discharge samples with gross beta concentrations in excess of 10 pCi/1.
Levels of radioactive materials in the sampled environmental media do not in-dicate the likelihood of public intakes in excess of 1% of those that could result from continuous annuni exposure to the concentration values listed in Appendix B, Table II, 10CFR20.
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n TABLE 1 RADIOIDOICAL DWIBONMENTAL )ONI'IORING SAMPLING AND ANALYSIS SLM1ARY JANUARY 1,1976 'ID JUNE 30, 1976 NUMBER OF NUMBER OF MEDIUM DESCRIPTION TYPE OF ANALYSIS FREQUENCY ~
SAMPLING IDCATIONS SAMPLES COLLECTED Air Continuous @
Gross Beta, I-131 Weekly 7
182 approx 1cfm Iake Water Composite Gross Beta, H-3 Monthly 3
18
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Well Water Grab Gross Beta Monthly 1
6 Milk Orab I-131, Sr-89/90 Monthly 4
23 Camma Isotopic Gamma Dose Continuoue TLD Monthly 13 90 Quarterly 13 30 Film Monthly 16 96 Aquatic Biota Orab Gross Beta, Sr-89/
Semiannual 5
23 90, camms Isotopic I
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n TABLE 2 HIGH, IDW AND AVERAGE CONCDITRATION FOR THE HIGHEDT AVERACE SAMPLING IDCATION JANUARY 1,1976 'ID JUNE 30, 1976 MEDIA TYPE OF ANALYSIS UNITS IDCATION HICH IDW AVERAGE pCi/m3 TR (50 mi SSW) 0.05
<0.01 0.o28 Gross (Beta-pC1/m3 All Air I-131 1) 4xnc Ick3 Water Gross Beta pCi 1 Discharge-129 21 49 H-3 pCi 1 Discharge 820 180 480 Well Water Gt-oss Beta pCi/1 Site 7
<3 4.3 Milk I-131(2) pC1/1 An 4.MDL Cs-137 LK (3.5 mi E) 12 45 9.2 Sr-89 GS(2.3 mise) 9
<5 45 Sr-90 LK (3 5 mi E) 16 9
n.4 Camma Dose TLD(monthly) day E(siteboundary) 191 117 159 TLD(quarterly) ay E (site boundary) 174 130 152 Film (monthly)
NM (3 mi E) 55 0
1.2 Biota (3)
Itriphyton Cross Beta pCi/g(vet)
Discharge 41 51 Discharge Algea(b) 18 Fish Discharge fmiN, Discharge 14 Shore Minnows mi N 14 Crayfish u
FOTES:
(1) Minimum Detectable Level (MDL) = 0.02 pC1/m3; some samples may have higher MDLs due to extended shipping time.
(2 MDL = 0 5 pCi/1; some samples may have higher MDLs due to extended shipping time.
(3 one sample per location.
(4 Only location where fish samples were obtained.
n TABLE 3 COMPARISON OF MEASURED AND CAICULATED IAKE WATER CONCDITRATIONS SAMPLING PERIOD CTSS BETA CONCDFPRATION CIBCULATING DISCHARGE WATER UrAITP FUTISH MEASURED CAICUIATED DISCHARGE FIDW RATE (MCD)
IITTAKE DISCHARGE AVERAGE MAXDtUM HIGH IDW AVERAGE 1/2/76 2/12/76 24 23 24 23 52 340 73.4 29 60.5 2/13/76 3/11/76 107 2 5 129 1 5 30 1070 68.1 29 35.0 3/12/76 4/07/76 10 + 2 26 + 3 9.3 420 43.9 o.4 28.5 4/o8/76 5/13/76 13 2 2 67 2 4 120 1630 37.8 2.9 8.5 5/14/76 6/10/76 6 f2 2513 89 6200 72.0 2.9 34.7 6/11/76 7/07/76 8 32 21 1 2 17 1350 72.0 40.8 66.1 Average 28 49 28 6200 73.4 o.4 39.7
m TABLE 4 RADIONUCLIDES IN WATER SAMPLES ColfrAINING GROSS BETA CONCDITRATIDNS IN EXCESS OF lo pCi/1 COLLECTIDN pC1/1 DATE IDCATION oross B Cs-134 cs-137 co-60 Mn-54 other oamma*
sr-89 sr-90 I-131 (a) 02 76 STLwI 24 + 3 8+1 20 + 2
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76 srLW 2473 5 71 15 72
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erLWI 107 7n 30 7 8 90 7 20
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<5 3 T1
<5.0 03 76 STLW 129 7 11 40 7 5 110 7 20
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<5 271
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04 76 sTLW 26 7 3 43
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<o.5 os 76 srLWI 1372 15 + 2 46 + 3
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<o.12(b) o5 76 srLm 67 74 2 T 0.2 6 7 0.4 <5 45 45 45 371
<o.12(b) 73 6 7 0.4 19 7 1.0
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<1 41 42 (I
44.2 06 76 sTLW 25 } 2 5 [+ 1 14[+1
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'1 5(c) o 76 srLW 21 (a) as of collection date (b)asof6/23/76 (c) as of date of analysis; insufficient sample remaining for more sensitive analysis
- The spectruen is computer scanned from @ to 6 kev.
specifically included are Ce-144, Ba-Im-1ko, Cs-134, l.
Cs-137, Zr-ND-95, Co-58, Co-6o, Mn-54, Zn-65. Ihturally-occurring gamma emitters such as K 40 and Ba daughters are frequently detected but not listed here.
Data listed as " < " are at the 3e level, othe'.s are 2 8.
Listed concentration is for Co-137 and may be slightly more or less sensitive for other nuclides.
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NRC eonu 195 u.s. NUCLE An ttcVL AT&;'Y E KISSloN DOCKET NUM:t;:
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NRC DI,STRIBUTION eon PART 50 DOCKET MATERIAL FROM: Consumers Pwr Co DATE oP oocuutNT Ta: MRC Jackson, Mich 1-11-77 R B Sewell oATE REcrivEog,g7,77 JBLETTEn
.O NoTORIZ E D PROP INPUT F06u NUMBER oF COPIES RECEIVED ConlciN AL EUNcLASSIFIED D:orY one signed DES 3;:lPTION ENCLOSURE Ltr te their 8-31-76 submittal....trans the Info regarding radioactive waste shipments following:
& radiological environmental monitoring...
.... for addition to e f fluent summaries of their 8-31-76 submittal........
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